• 제목/요약/키워드: Radiation Accident

검색결과 303건 처리시간 0.029초

핵사고시 매스컴의 보도경향과 본질적 면에서 본 국민이해의 관점 (특히 한국신문 보도에 관련된 정량적인 분석의 사례를 중심으로) (On the Report Tendency of Mass Communication in Nuclear Accident and the Standpoint of Public Acceptance from a Intrinsic Point of View. (A Case Study of Quantitative Analysis in Connection with the Newspaper Report Especially in Korea.))

  • 이수용
    • Journal of Radiation Protection and Research
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    • 제21권3호
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    • pp.217-253
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    • 1996
  • 체르노빌 핵사고직후 대형 핵사고에 대한 반응은 이 사고가 정치, 경제 및 사회적 요인에 밀접하게 관련된 대중정보에 어떻게 영향을 주는가의 극명한 사례가 되었다. 오늘날 다양한 정보화 시대에 살면서도 '핵'에 관한 한 정보원의 수용은 항상 제한 받는 경향에 있다. 그러므로 본 조사에서는 보도원으로부터 수용된 미확인보도 내지는 과장된 핵사고 상황보도 등의 문제로 파급될 수 있는 심리적인 동요와 혼란을 극소화할 수 있는 방법과 대책을 모색하여 개연성(probability)이 상존하는 크고 작은 핵사고의 경우에 대비코자 하는 한 사례로 삼고자 하였다. 또한, 핵사고시 제시된 방사선 제반분야에 대한 총망라된 보도영역에서 과학기사 보도 작성지침으로서의 관련 학술용어의 가능한 사용한도를 표로써 설정하였고, 아울러 본질적인 면에서 본 국민이해와 방사선 재해방지 홍보대책과 더불어 몇 가지 방법론을 거론하였다.

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Thyroid Doses in Children from Radioiodine following the Accident at the Fukushima Daiichi Nuclear Power Plant

  • Kim, Eunjoo;Kurihara, Osamu
    • Journal of Radiation Protection and Research
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    • 제45권1호
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    • pp.2-10
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    • 2020
  • Background: Huge amounts of radionuclides were released into the environment due to the Fukushima Daiichi Nuclear Power Plant (FDNPP) accident, which caused not only serious contamination on the ground, but also radiation exposure to the public. One problem that remains in performing the dose estimation is the difficulty of estimating the internal thyroid dose due to the intake of radioiodine (mainly, 131I) because of limitations to the human data available. Materials and Methods: The relevant papers were collected and reviewed by the authors. The results of thyroid dose estimates from different studies were tabulated for comparison. Results and Discussion: The thyroid dose estimates from the studies varied widely. The dose estimates by the United Nations Scientific Committee on the Effects of Atomic Radiation were higher than the others due to the ingestion dose being based on conservative assumptions. The dose estimates by Japanese experts were mostly below 20-30 mSv. The recent studies suggested that exposure on March 12, 2011 would be crucial for late evacuees from the areas near the FD-NPP because of the possible intake of short-lived radionuclides other than 131I. Further multilateral studies are vital to reduce uncertainties in the present dose estimations. Conclusion: The estimation of the thyroid doses to Fukushima residents still has many uncertainties. However, it is considered unlikely that the thyroid doses exceeded 50 mSv except in some extreme cases. Further multilateral studies are thus necessary to reduce the uncertainties in the present dose estimations.

Dose Estimation Model for Terminal Buds in Radioactively Contaminated Fir Trees

  • Kawaguchi, Isao;Kido, Hiroko;Watanabe, Yoshito
    • Journal of Radiation Protection and Research
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    • 제47권3호
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    • pp.143-151
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    • 2022
  • Background: After the Fukushima Daiichi Nuclear Power Plant (FDNPP) accident, biological alterations in the natural biota, including morphological changes of fir trees in forests surrounding the power plant, have been reported. Focusing on the terminal buds involved in the morphological formation of fir trees, this study developed a method for estimating the absorbed radiation dose rate using radionuclide distribution measurements from tree organs. Materials and Methods: A phantom composed of three-dimensional (3D) tree organs was constructed for the three upper whorls of the fir tree. A terminal bud was evaluated using Monte Carlo simulations for the absorbed dose rate of radionuclides in the tree organs of the whorls. Evaluation of the absorbed dose targeted 131I, 134Cs, and 137Cs, the main radionuclides subsequent to the FDNPP accident. The dose contribution from each tree organ was calculated separately using dose coefficients (DC), which express the ratio between the average activity concentration of a radionuclide in each tree organ and the dose rate at the terminal bud. Results and Discussion: The dose estimation indicated that the radionuclides in the terminal bud and bud scale contributed to the absorbed dose rate mainly by beta rays, whereas those in 1-year-old trunk/branches and leaves were contributed by gamma rays. However, the dose contribution from radionuclides in the lower trunk/branches and leaves was negligible. Conclusion: The fir tree model provides organ-specific DC values, which are satisfactory for the practical calculation of the absorbed dose rate of radiation from inside the tree. These calculations are based on the measurement of radionuclide concentrations in tree organs on the 1-year-old leader shoots of fir trees. With the addition of direct gamma ray measurements of the absorbed dose rate from the tree environment, the total absorbed dose rate was estimated in the terminal bud of fir trees in contaminated forests.

Occupational Dose Analysis of Spent Resin Handling Accident During NPP Decommissioning

  • Hyunjin Lee;Chang-Lak Kim;Sang-Rae Moon;Sun-Kee Lee
    • 방사성폐기물학회지
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    • 제21권2호
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    • pp.247-253
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    • 2023
  • According to NSSC Notice No. 2021-10, safety analysis needs to be introduced in the decommissioning plan. Public and occupational dose analyses should be conducted, specifically for unexpected radiological accidents. Herein, based on the risk matrix and analytic hierarchy process, the method of selecting accident scenarios during the decommissioning of nuclear power plants has been proposed. During decommissioning, the generated spent resin exhibits relatively higher activity than other generated wastes. When accidents occur, the release fraction varies depending on the conditioning method of radioactive waste and type of radioactive nuclides or accidents. Occupational dose analyses for 2 (fire and drop) among 11 accident scenarios have been performed. The radiation doses of the additional exposures caused by the fire and drop accidents are 1.67 and 4.77 mSv, respectively.

APPLICATION OF WHOLE BODY COUNTER TO NEUTRON DOSE ASSESSMENT IN CRITICALITY ACCIDENTS

  • Kurihara, O.;Tsujimura, N.;Takasaki, K.;Momose, T.;Maruo, Y.
    • Journal of Radiation Protection and Research
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    • 제26권3호
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    • pp.249-253
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    • 2001
  • Neutron dose assessment in criticality accidents using Whole Body Counter (WBC) was proved to be an effective method as rapid neutron dose estimation at the JCO criticality accident in Tokai-mura. The 1.36MeV gamma-ray of $^{24}Na$ in a body can be detected easily by a germanium detector. The Minimum Detectable Activity (MDA) of $^{24}Na$ is approximately 50Bq for 10miniute measurement by the germanium-type whole body counter at JNC Tokai Works. Neutron energy spectra at the typical shielding conditions in criticality accidents were calculated and the conversion factor, whole body activity-to-organ mass weighted neutron absorbed dose, corresponding to each condition were determined. The conversion factor for uncollied fission spectrum is 7.7 $[(Bq^{24}Na/g^{23}Na)/mGy]$.

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Assessing the Activity Concentration of Agricultural Products and the Public Ingestion Dose as Result of a Nuclear Accident

  • Keum, Dong-Kwon;Jeong, Hyojoon;Jun, In;Lim, Kwang-Muk;Choi, Yong-Ho
    • Journal of Radiation Protection and Research
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    • 제43권2호
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    • pp.39-49
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    • 2018
  • Background: A model to assess the activity concentration of agricultural products and the public ingestion dose as result of a nuclear accident is necessarily required to manage the contaminated agricultural systems by the accident, or to estimate the effects of chronic exposure due to food ingestion at a Level 3 PSA. Materials and Methods: A dynamic compartment model, which is composed of three sub-modules, namely, an agricultural plant contamination assessment model, an animal product contamination assessment model, and an ingestion dose assessment model has been developed based on Korean farming characteristics such as the growth characteristics of rice and stockbreeding. Results and Discussion: The application study showed that the present model can predict well the characteristics of the activity concentration for agricultural products and ingestion dose depending on the deposition date. Conclusion: The present model is very useful to predict the radioactivity concentration of agricultural foodstuffs and public ingestion dose as consequence of a nuclear accident. Consequently, it is expected to be used effectively as a module for the ingestion dose calculation of the Korean agricultural contamination management system as well as the Level 3 PSA code, which is currently being developed.

후쿠시마 사고로 해양으로 누출된 137Cs에 의한 인체 위해도 평가 (Health Risk Assessment due to 137Cs Released into Ocean from the Severe Accident of the Fukushima Dai-ichi Nuclear Power Plants)

  • 민병일;이백근;서경석;박기현
    • 방사선산업학회지
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    • 제8권2호
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    • pp.123-132
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    • 2014
  • After the nuclear accident of the Fukushima Dai-ichi Nuclear Power Plants (FDNPPs) on 11 March 2011, a large amount of radioactive materials has been released into the atmosphere and the ocean. A compartment model is used to evaluate the circulation characteristics and the spatiotemporal concentration distributions of radionuclides in the ocean. In the comparison with observed concentrations of $^{137}Cs$ in seawater, calculated concentrations by the compartment model were well agreed with them. On the basis of these results, we performed evaluation of the effective dose and the cancer risk. In the early stage of the accident, the effective doses from ingestion of the seafood near the Fukushima region were much higher than 1 mSv which is the value of the annual effective dose limit to individual recommended by the International Commission on Radiological Protection (ICRP). However, the effective doses by ingestion of the seafood decreased below 1 mSv as distance from the FDNPPs increased and time passed. In addition, it was estimated that the cancer risks by intake of the contaminated marine products were less than natural occurrence probability of cancer. Consequently, it was inferred that the health risk due to the $^{137}Cs$ was low after since mid-term period of the accident.

저선량과 고선량 측정구간 변환이 가능한 모바일 방사선 측정시스템 개발 및 평가 (Development and Evaluation of a Mobile Environmental Radiation Measurement System That Can Switch between Low and High Dose Measurement Sections)

  • 이홍연;한상준;김보길;이건주;김석현;김정훈
    • 대한방사선기술학회지:방사선기술과학
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    • 제45권1호
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    • pp.49-55
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    • 2022
  • This study is to develop a mobile type environmental radiation measurement system for emergency response or environmental radiation monitoring of local governments near nuclear facilities. A mobile radiation measurement system can monitor radiation by field beyond the spatial constraints of a fixed environmental radiation monitor. If installed in local government infrastructure such as public transportation, environmental radiation can be monitored without additional manpower and measurement work. In addition, it is designed to enable monitoring and measurement of radiation from low to high doses as well as the environment in preparation for radioactive disasters such as nuclear power plant accidents. It is expected that this system will be utilized not only in normal times but also in the event of a radiation accident to improve the disaster prevention capabilities of local governments.

Comparative Analysis of Terminology and Classification Related to Risk Management of Radiotherapy

  • Oh, Yoonjin;Kim, Dong Wook;Shin, Dong Oh;Koo, Jihye;Lee, Soon Sung;Choi, Sang Hyoun;Ahn, Sohyun;Park, Dong-wook
    • 한국의학물리학회지:의학물리
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    • 제27권3호
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    • pp.131-138
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    • 2016
  • We analyzed the terminology and classification related to the risk management of radiation treatment overseas to establish the terminology and classification system for Korea. This study investigated the terminology and classification for radiotherapy risk management through overseas research materials from related organizations and associations, including the IAEA, WHO, British group, EC, and AAPM. Overseas risk management commonly uses the terms "near miss", "incident", and "adverse event", classified according to the degree of severity. However, several organizations have ambiguous terminologies. They use the term "near miss" for events such as a near event, close call, and good catch; the term "incident" for an event; and the term "adverse event" for the likes of an accident and an event. In addition, different organizations use different classifications: a "near miss" is generally classified as "incident" in most cases but not classified as such in BIR et al. Confusion might also be caused by the disunity of the terminology and classification, and by the ambiguity of definitions. Patient safety management of medical institutions in Korea uses the terms "near miss", "adverse event", and "sentinel event", which it classifies into eight levels according to the severity of risk to the patient. Therefore, the terminology and classification for radiotherapy risk management based on the patient safety management of medical institutions in Korea will help in improving the safety and quality of radiotherapy.